Radiation Induced Segregation at Grain Boundary in an Austenitic Stainless Steel under Ion Irradiation
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<BR>Chromium depletion near grain boundaries of austenitic stainless steel during irradiation was investigated. Specimens were kept at 1, 473 K for 30 min, and were quenched into the water. Irradiations were done using 400 keV He+ ions at 573, 673 and 773 K up to 10 dpa with a dose rate of 2.4 ×10-4 dpa/s. After irradiation, the Cr concentration profile near the grain boundary was measured using an analytical electron microscope with a 1 nm beam diameter. At 573 K, Cr depletion is small, and its concentration at the grain boundary decreases to 15.5 mass% at 3 dpa from the initial concentration of 18.5 mass%. At 673 and 773 K, Cr concentration at the grain boundary rapidly decreases between 0 and 0.2 dpa, and then gradually approaches a constant value, 7.0 mass% at 673 K and 5.0 mass% at 773 K. Two stages are found in radiation induced segregation (RIS) behavior, one stage in which Cr depletion and Ni enrichment balance and another in which Fe depletion and Ni enrichment balance. <BR>These experimental results were compared with the calculations based on the vacancy-induced inverse Kirkendall effect. Predicted Cr segregation at 673 and 773 K above 3 dpa agrees with the experimental results. But Cr depletions at low doses which were obtained in the experiments are much faster than calculated. At 573 K in the experiments, depletion is smaller than calculated up to 10 dpa.
- Journal of Nuclear Science and Technology
Journal of Nuclear Science and Technology 33(6), p.474-478, 1996-06-25
Atomic Energy Society of Japan